ML20133B843

Insp Rept 50-267/85-19 on 850625-0703.No Violation or Deviation Noted.Major Areas Inspected:Surveillance Procedures & Records,Ie Bulletin & Generic Ltr Followup, Plant Staff Readiness to Operate & Maintain Plant & Tours

ML20133B843
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/30/1985
From:	Farrell R, Jaudon J, Plumlee G, Skow M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20133B767	List: IR 05000267/1985019 ML20133B766
References
50-267-85-19, GL-82-33, GL-83-28, GL-84-24, GL-85-02, GL-85-2, IEB-79-01, IEB-79-01A, IEB-79-01B, IEB-79-1, IEB-79-1A, IEB-79-1B, IEB-80-11, NUDOCS 8508060271
Download: ML20133B843 (6)

See also: IR 05000625/2007003

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APPENDIX

U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

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NRC Inspection Report: 50-267/85-19 License: DPR-34

Docket: 50-267

Licensee: Public Service Company of Colorado

P. O. Box 840

Denver, Colorado 80201

-Facility Name: Fort St. Vrain Nuclear Station

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Inspection At: Fort St. Vrain Nuclear Generating Station, Platteville,

Colorado ,

Inspection Conducted: June 25 - July 3, 1985

Inspecto s: . /JJJ /& 7 3d $$

g E. Fa ell, Senf6r Resident Inspector

(pa[rs.2.b,4, nd 5)

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g. P( Jatj60ii, Chief,' Project Section A D 5te,

(pars.(4 and 5)

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G. P1 lee III, Reactor Inspector Date

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M. E. Skow, Reactor Inspector

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(par. 2.a)

8508060271 850801

PDR ADOCK 05000267

G PDR

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Assisted by: .W. A. Spencer, Consultant

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-Approved:

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y,0 R. E.. Ireland, Chief. Engineering Section, Reactor Date '

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,/ Project Branch

Inspection Summary

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InspectionConductedJune25-July 3,1985(Report 50-267/85-19) ,

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Areas-Inspected: Special announced inspection of surveillance procedures and

records, IE Bulletin and Generic Letter followup, plant staff readiness to

operate and maintain the plant, and plant tours. The inspection involved 85

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. inspector-hours onsite by four NRC inspectors and one NRC consultant.

Results: Within the areas inspected, no violations or deviations were -

identified.

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DETAILS

1. Persons Contacted

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Principal Licensee Employees -

J. Gahm, Manager Nuclear Production

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• L. Singleton, Manager Quality Assurance

F. Novachek, Technical / Administrative Services Manager

• F.. Borst, Support Services Manager

• C. Fuller, Station Manager-

• M. Ferris, Quality Assurance Operations Manager

S. Willford, Training Supervisor

• D. Evans, Superintendent Operations

• W. Franek, Superintendent, Plant Scheduling and Stores

• R. Craun, Nuclear Site Engineering Manager

• S. Hofstetter, Nuclear Licensing Engineer

• J. Eggebroten Superintendent, Technical Services Engineering

• Denotes attending the exit interview held on June 28, 1985.

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4 2. Surveillance Procedures and Records  !

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a. Control Rod Drive Mechanisms (CRDMs)

Test-RP-5, " Control Rod Drive Checkout," has been completed for all

of the rods that have been refurbished and are currently installed in

the core. RP-5 meets the requirements set forth in the existing

Technical Specifications. The licensee has committed to interim

Technical Specifications for control rods in their letter P-85180,

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dated June 7, 1985. The licensee committed to operate the facility

in accordance with procedures based on those interim Technical

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Specifications prior to plant restart. The licensee also stated that

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all appropriate tests on their CRDMs will be performed meeting the

requirements of the interim Technical Specifications prior to

restart. The new procedures are in preparation. Review of these

surveillance procedures and results remains an open item (8519-01).

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b. Existing Technical Specification Surveillances

A survey of licensee records indicates:

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. Licensee is utilizing approved procedures to perform technical

specification surveillances.

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. Licensee activity performing technical specification surveil-

lances has continued throughout the current. extended outage.

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.- Surveillances required and possible are maintained current. It

g is not possible to do all surveillances when the reactor is not

, at power. Additionally, it is not possible to perform surveil-

' lances'on equipment which is dismantled / removed for overhaul.

The licensee is currently proving systems operable and restoring

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plant configuration in preparation for restart. Interviews with

plant and nuclear power production division management indicate the -

licensee's intent and understanding of the requirement to have all

surveillances current at restart.

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Verification that surveillances are current is considered an open

item (8519-02).

' Surveillance records reviewed included:

. Reserve Shutdown System

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Prestressed Concrete Reactor Vessel (PCRV) & PCRV Penetration

Overpressure Protection

. Helium Circulator Water Turbine Drives

. Bearing Water Makeup Pump

. Firewater System / Fire Suppression Water System

. PCRV Closure Leakage

. Alternate Cooling Method (ACM) Diesel Driven Generator

. ACM Hard Valve and Transfer Switch

. Fire Water Booster Pump

. Circulating Water Makeup System

. Safe Shutdown Cooling Valves

. Hydraulic Power System

. Reactor Building Exhaust Filter

. Standby Diesel Generators

. Station Batteries

No violations or deviations were identified in this area.

3. IE Bulletin and Generic Letter Followup

All the open Bulletins and Generic Letters at Fort St. Vrain have been

. answered by the licensee with those currently under review by the NRC

staff.

. Bulletin 79-01/-01A/-01B " Environmental Qualification of Class 1E

Equipment"

. Bulletin 80-11 " Masonry Wall Design"

. Generic Letter 82-33 - Supplement 1 to NUREG-0737 " Requirements For

Emergency Response Capability"

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, . Generic Letter 83-28 " Required Actions Based on Generic Implica-

'tions of Salem'ATWS Events"

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. Generic Letter 84-24 " Certification'of Compliancefto 10 CFR 50.49,

Environmental Qualification of Electric Equipment Important to

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Safety For Nuclear Power Plants"

. Generic Letter'85-02 " Staff. Recommended Action Stemming From NRC

Integrated Program For-the Resolution of Unresolved Safety Issues

Regarding Steam Generator Tube Integrity"

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All' responses by the licensee met the Bulletin / Generic Letter time

requirements-or subsequent licensee commitment time requirements.

No violations or deviations were identified.

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4. . Plant Staff Readiness to Operate and Maintain the Plant

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u+ The plant' staff's readiness to operate and maintain the facility was'

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reviewed. A special startup training program was completed for the

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, licensed operators. This program was reviewed by (a) actual attendance ati

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a class session, (b) review of lesson plans and backup material for all -

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', sessions, (c) review of examinations,'and (d) discussion of results with. '

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. both. operators'and training staff. This program included: *

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4l; a. Discussion of completed plant modifications.

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b. Actual Overall Plant and System Operating Procedures.

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c. Control room mockup so that pertinent gauge readings and switch

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,( manipulations could be integrated with classroom discussion.

'~". d. Discussion of technical specification requirements. ,

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'I Additional training'will be necessary to cover plant protective system

setpoints and the final CROM surveillance procedures. The program will>

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equip the operators to safely operate the plant.

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Sufficient ~ trained staff are available to provide necessary shift manning.

No violations or deviations were identified in this area.

5. Plant Tours

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-The NRC inspectors toured the plant to observe housekeeping, fire protec-

tion, and' general job practices.

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Inspectors familiar'with the plant for more than 1 year noted consider-

able improvement in plant appearance and housekeeping practices.

The plant has been shutdown with major modifications in progress for over

a year. Consequently, all equipment tag status and system configurations

should be verified prior to restart. Plant management has advised the SRI

that this is being done by the plant staff.

No violations or deviations were identified in this area.

6. Exit Interview

Exit interviews were conducted on June a' '1985, and July 3, 1985, at

.which time the inspectors reviewed the scope and findings of the

inspection.

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